ML041620486
| ML041620486 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/02/2004 |
| From: | Conicella N Public Service Enterprise Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-272/04-301 | |
| Download: ML041620486 (46) | |
Text
Appendix D Form ES-D-I Facility:
SALEM I
& 2 Scenario No.:
NRC #I Op-Test No.: HOTEL Examiners:
Operators:
Initial Conditions:
85% Rated Thermal Power, BOL, Equilibrium Conditions Turnover:
Unit 2 is at 85% power with the following equipment is out of service: 2A EDG taken 00s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance, 21 RHR Pump taken 00s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for coupling alignment. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now. All required surveillances are complete. Weather conditions are normal. Unit 1 is at 100% power. Hope Creek is in a refueling outage. Shift orders are to raise power to 100% at 10% per hour.
Event Type*
N CRSlPO R
RO 2
PRO01 6B I
CRSlRO 3 I SJO18OC C
CRSlPO RP0073 RP0059A&B RP0058 C
ALL
~~
M ALL C
CRSlPO 1
(N)ormal, (R)eactivity, (1)nstrumen
~~
Event Description Raise Reactor Power Pressurizer Pressure Channel 111 Fails Low (TS CRS) 23 SI Accumulator Gas Leak (TS CRS)
Decreasing Condenser Vacuum Spurious Turbine Trip, ATWT, Pzr Safety 2PR3 Fails Open 21 AFW Pump Fails To Auto Start Terminate after SI flow reduction evaluation in LOCA-1 (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Revision 9
SIMULATOR SETUP
- 1.
- 2.
- 3.
- 4.
INITIAL CONDITIONS Initialize simulator to IC-xxx, 85% power, BOL, C, xxx ppm Clearance tag 2A EDG Clearance tag 21 RHR Pump Pzr Press and Level Ch Ill selected for control and recorder
- 1.
PZR Safety Valve 2PR3 fails open when Reactor trips (Control Bank D 5 steps)
Description
- 5.
- 6.
- 7.
I Delay I Ramp PROOZOA, Pzr Safety Valve 2PR3 Fails No No No/l True True Open PROOl6B, Pzr Press Ch Ill (PT459) Fails No No 1 /No NA 1700 Low SJO18OC, 23 SI Accumulator Gas Leak No No UNO NA 4
RP0073, Main Turb Trip Failures No No RP0059A, Failure of Man Rx Trip No No No/No Final Value 4
True
)3.)RP0059B,Failure of Man S i l k Trip No No No/No -1 True True I 4. I RP0058, Failure of Auto Rx Trip' I
No I No I No/No I True True CN0086, Loss of Main Condenser 18-I Vacuum2 I
No I 00:03:00 I 3/No I 0 I 50 Page 2 of 10 NUREG-1021, Revision 9
- 2.
RPIOD, 22 MG Set Gen Output Bkr No No
- 3.
RP07D, 21 MG Set Motor Bkr No No
- 4.
RP08D, 22 MG Set Motor Bkr No No 110 OVERRIDE
SUMMARY
I 5/No Close Trippe 6/No Start Stop 7/NO Start Stop d
No I.
- 2.
- 3.
- 4.
SIMULATOR OPERATOR NOTES I
Description Delay Ramp Remote Initial Final
/Event Value Value 6440, OVDl RTB A Trip Switch No No No/No Off Off 6440, OVDI RTB A Trip Switch No No No/No Off Off C310.2E6D Pressure Heater Bus 480V No No No/No Off Off Open Switch C510,2G6D Pressure Heater Bus 480V No No No/No Off Off Open Switch 1
Open Reactor Trip Breakers when the crew has reached Step 14 (reactivity insertion step).
Delete overrides on RBs, then B449, B441, RTB A and B open switch to ON. Also, open all Rod Drive MG Set Breakers:
RT-4, RP007D 21 Motor RT-5, RP008D 22 Motor RT-6, RPOO9D 21 Output RT-7, RPOIOD 22 Output
- 2.
- 3.
Once the crew has dropped load by approximately 10% on decreasing vacuum, change RT-3 Final Value = 100, Ramp = 0O:OO:OO If requested, turn power off to 2PR6 using Remote Function PR34D, PORV Stop Valve toggled to Tagged.
- 4.
Collect trend data on the following for evaluators:
Reactor Power Turbine Generator Load (MW)
Condenser Vacuum Pressurizer pressure (not Ch 111)
Page 3 of IO NUREG-1021, Revision 9
11 Op-Test No.: I Scenario No.:
1 Event No.:
1 Time Event
Description:
Unit is at 85% power. Shift orders are to raise power to 100% at 10% per hour.
Position Applicant's Actions or Behavior CRS Directs activities associated with power increase
- rod motion
- dilution
-turbine loading
- rod motion
- dilution RO Adds positive reactivity PO CRS
~~
Coordinates with RO to initiate power increase
- operate turbine controls to establish loading rate Makes necessary notifications
- load dispatcher
- operations management Page 4 of 10 NUREG-I 021 I. Revision 9
Op-Test No.:
1 Scenario No.: I Event No.:
2 Time Position RO RO Event
Description:
Pressurizer Pressure Channel 111 Fails Low Applicant's Actions or Behavior Responds to alarms.
Identifies failure of Pzr Press Ch 111 RO RO CRS Places Pzr Press Master Controller in MANUAL, adjusts demand to I current Dressure.
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Selects alternate pressure channel for pressure control Places Master Controller in AUTO Directs removal of the failed Pressurizer Pressure Channel from service IAW S2.0P-SO.RPS-O003(Q), Placing Pressurizer Channel In Tripped Condition CRS CRS CRS/RO CRS/RO Implements AB.PZR-0001. Directs RO to
- adjust Master Controller output to value obtained from Attachment 1
- select alternate pressure control channel
- return Master Controller to AUTO Refers to TS. Enters TSAS 3.3.1.I.
Action 6 and 3.3.2.1 b. Action19 for failed channel. Enters TSAS 3.4.5b for PORV 2PR1 not operable in AUTO.
Close 2PR6 PORV Stop Valve Direct NE0 to open breaker for power to 2PR6 PORV Stop Valve Page 5 of 10 NUREG-1021, Revision 9
Scenario No.:
1 SI Accumulator Gas Leak Event No.:
3 Position C RS/RO/PO PO PO Op-Test No.:
1 Event
Description:
23 L
PO CRS/PO CRS Applicant's Actions or Behavior Recognize indications of problem with decreasing pressure on 23 SI Accum
- Control Console 2CC1 Bezel 1-1 1 alarm for 23 ACCUM PRESSURE HI/LOW
- indicated Dressure on 2PT-936C and 2PT-937C Refers to S2.OP-AR.ZZ-0011 (Q) for 23 ACCUM PRESSURE HVLOW NOTIFY the SM/CRS to refer to Technical SDecifications Refers to S2.OP-SO.SJ-O002(Q), Accumulator Operation, to restore normal rxessure in 23 Accumulator Raises pressure per procedure:
ENSURE CLOSED 2NT35, N2 HDR ENSURE OPEN one of the following valves:
- 2NT49, UNIT 2 N2 B/U SUP TO ACCUM OR OPEN 2NT32, N2 SUPPLY OPEN 23SJ93, N2 SUPPLY CLOSE2NT32
- INTZ, UNIT 1 N2 SUPPLY TO UNIT 2 ACCUM When desired pressure is achieved, CLOSE 23SJ93, N2 SUPPLY Have second operator perform independent verification IAW, Section 8.0 Refer to TS 3.5.1. for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action requirement for inoperable accumulator Page 6 of 10 NUREG-1021, Revision 9
Position C RS/RO/PO CRS Op-Test No.: 1 Scenario No.:
1 Event No.:
4 Event
Description:
Decreasing Condenser Vacuum PO RO Applicant's Actions or Behavior Recognize indications of decreasing vacuum:
- primary temperature
- steam line pressure
- rise in condenser backpressure
- Alarm OHA G-5, CNDSR VAC LO
- Alarm OHA G-13, CNDSR VAC LO-LO Implements S2.OP-AB.COND-0001 (Q), Loss of Condenser Vacuum.
Directs actions IAW procedure
- initiates Attachment I, Continuous Action Summary
- dispatches operators to look for source of problem per Attachment 2
- directs start of all available condenser vacuum pumps
- directs load reduction at 5 5% per min to attempt to stabilize condenser press
- when required (backpressure > limit in Att 4), initiate rapid load reduction
- implement S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction
- when necessary, orders manual reactor and turbine trips Performs actions as directed to address decreasing vacuum:
- dispatches operators to look for source of problem per Attachment 2
- starts all available condenser vacuum pumps
- performs turbine load reduction Performs actions as directed to address decreasing vacuum:
- dispatches operators to look for source of problem per Attachment 2
- coordinates with PO to reduce turbine and reactor power
- maintains Tavg on program
- energizes pressurizer heaters
- initiates boration Page 7 of 10 NUREG-1021, Revision 9
Position RO CRS PO RO RO RO CRS/PO CRS/PO RO RO CRS CRS CRSIROIPO RO ADDlicant's Actions or Behavior Performs initial actions of EOP-TRIP-1
- 1. MANUAL Reactor Trip:
First Handle to Trip.
RTBs to open.
Second Handle to Trip.
E6D and G6D to open.
- 2. Trip not confirmed.
- 3. MANUAL Turbine Trip.
- 4. Trip not confirmed.
- 5. Initiate Main Steam Line Isolation
- 6. Initiate Control Rod Insertion.
Transitions to EOP-FRSM-I CRITICAL TASK #I Main Steam Line Isolation signal manually actuated within 60 seconds of diagnosis of ATWT conditions.
PO reports 21 AFW Pump tripped.
Starts 23 AFW PumD and verifies flow >44E4 Ibm/hr Starts 21 and 22 Charging Pumps Verifies BIT flow and SJ1.2.4.5. 12. 13 oDen Verifies CV40,41,68 &69 closed Dispatches NE0 to open RTBs and Rod Drive MG Set Breakers Dispatches NE0 to close WR70 and1 51 s Determines that Primarv Safetv Valve 2PR3 is stuck oDen Verifies all PRNls < 5%
Verifies IR startup rate negative Directs chemistry to sample RCS Directs STNRx Eng to perform SDM calculation Returns to EOP-TRIP-1 Verify immediate actions of EOP-TRIP-1 Closes 2CV139 & 2CV140 with RCS pressure 4 500 psig Page 8 of 10 NUREG-1021, Revision 9
Op-Test No.: 1 Scenario No.: 1 Event No.:
5 Event
Description:
Spurious Turbine Trip, A M, Pzr Safety 2PR3 Fails Open CRITICAL TASK #2 With RCS Pressure less than 1350 psig and BIT flow established, secure RCPs prior to exiting EOP-TRIP-I the second time..
RO CRS/RO/PO
~
CRS/RO/PO Stops all RCPs with RCS pressure 4 350 psig Verifies equipment alignment per EOP-TRIP-1 Performs diagnostic activities including:
LOSC SGTR LOCA Transitions to EOP-LOCA-1 Performs faulted SG evaluation Performs ruptured SG evaluation Resets SI, Phase A, Phase B, opens 21 and 22 CA330, and resets each I SEC and resets 230V Control Centers I
CRS RO/PO CRS/RO/PO Performs SI flow reduction evaluation NOTE Terminate scenario on lead evaluators direction after crew has determined that SI flow cannot be reduced.
Page 9 of 10 NUREG-1021. Revision 9
Op-Test No.:
1 Scenario No.:
1 Event No.:
6 Event
Description:
21 AFW Pump Fails To Auto Start Time
~
Position Applicant's Actions or Behavior NOTE: 21 AFW Pump trip should be addressed during the A M
(Event #5)
PO reDorts 21 AFW PumD trimed.
PO CRS PO NOTE Terminate scenario on lead evaluator's direction after crew I has determined that SI flow cannot be reduced.
~
~~
Directs start of 23 AFW Pump.
Starts 23 AFW Pump and verifies flow >44E4 Ibm/hr..
Page 10 of 10 NUREG-1021, Revision 9
Appendix D Form ES-D-1 Event Malf. No.
No.
1 NIOI 93A 2
3 TU0081H Facility:
SALEM I
& 2 Scenario No.:
NRC #2 Op-Test No.: HOTEL I/
Event Type*
I CRSlRO N
CRSlPO R
RO Examiners:
Operators:
4 5
6 7
I' Initial Conditions:
Turnover:
magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 00s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement. AFW pump maintenance is expected to be complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from now. All required surveillances are complete. The crew is directed to maintain 100% Rated Thermal Power, BOL, Equilibrium Conditions Unit 2 is at 100% power. Unit 1 and Hope Creek are also at 100% power. Solar VLQ447 C
RP0058 CRSlPO RP0069 RP0279A RP0279B RD0064 C
EL0273A C
EL0260 CRSlPO EL0261 AF0183 M
EL01 61 ALL CRSlRO Event DescriDtion PRNIS Channel N41 Fails High (TS CRS)
NE0 Reports Broken Snubber in Aux Building (TS CRS)
Main Turbine Governor Valve 24MS29 Fails Closed SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip, Auto MSLIS Fails to Actuate
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2 Control Rods Fail To Fully Insert On Reactor Trip Loss of 2A 4 W Vital Bus Offsite sources. 21 EDG fails to auto connect with vital bus Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDGl Terminate when feed flow reestablished to a SG (C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9
INITIAL CONDITIONS r
- 2.
- 3.
Clearance tag 22 AFW Pump Ensure 2N41 NOT selected on NIS Recorder 2NR45 NlOl93A, Power Rng Ch N41 Fails High TU0081 H, 23MS29 Turb Cntrl Vlv Fails CIS VL0447,22BF19 Fails Closed3 EL0260,4KV Breaker 24ASD Failure EL0261,4KV Breaker 23ASD Failure No No 1 /No NA 200 No No 2/No NA True No 00:00:03 3/No NA 0
No No No/l NA True No No No/l NA True
- 14.
I No 4/NO EL0161,2A Emer Diesel Generator Trip' No SIMULATOR SETUP I 1.
I Initialize simulator to IC-1 81, 100% power, BOL, C, 11 52 ppm I
EVENT TRIGGERS I
- 1. I 2A 4KV Bus Deenergizes on Reactor Trip (Control Bank D < 5 steps)
I MALFUNCTION
SUMMARY
No -
- 1.
- 2. -
- 3.
- 4.
- 5.
I Description Remote I Event Initial Value Final Value RP0058, Failure of Auto Rx Trip No/No NA True RP0069. Main Turbine interface Valve Failure NolNo NA True No/No NA 4
RD0064, Any Rod Fails To Trip (Stuck)
RD0064, Any Rod Fails To Trip (Stuck)
RP0279A, Auto MSLIS Fails to Actuate -
Trn A No/No NA 44 No/No NA True RP0279B, Auto MSLIS Fails to Actuate -
1 No 1
No I No/No 1 NA 1 True I I Trn B 1 IO.
- 11.
I 12. I EL0273A, 2A DG Bkr Fails To Auto-Close No I NO 1 NO/Nol N A T T r u e I 13. I AFOl83,23 Aux FW Pmp Overspeed Trip' I No
~~
N A T T r u e No Page 2 of 11 NUREG-1021, Revision 9
REMOTE FUNCTION
SUMMARY
I I
I I
I I
Description AF0025D, 22 AFW Pump Bkr Control Power AF0026D, 22 AFW Pump Rack Out No -
- 1. -
- 2. -
Delay Ramp Remote Initial I Event Value No No No/No On No No No/No xxxx No
- 1.
Final Value Description Delay Ramp Remote Initial Final
/Event Value Value None Off 110 OVERRIDE
SUMMARY
I I
I I
I I
SIMULATOR OPERATOR NOTES I
- 1.
- 2. -
Trip EDG and 23 AFW Pump shortly after 2A 4 W Bus is re-energized post-trip.
After being dispatched to investigate closure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 24MS29 valve actuator.
~
Insert Malf VL0447 (Remote #3) after condensate pump stopped during rapid power reduction or at lead examiner's discretion.
- 4.
~
~
Collect trend data on the following for evaluators:
Reactor power Turbine Generator load (MW) 21,22,23,24 SG NR level 21,22,23,24 SG WR level Page 3 of 11 NUREG-I 021, Revision 9
Position CRS/RO RO RO CRS CRS CRS CRS/PO
~~
~
CRS/RO/PO Applicant's Actions or Behavior Observe indications of channel failure
- numerous alarms on OHA-E
- control rods stepping in
- PR NIS N41 indicating full scale high
- PCS AFD alarms Determines PR NIS Channel has failed high. Places ROD BANK SELECTOR SWITCH in MANUAL after obtainina CRS concurrence.
Op-Test No.:
1 Scenario No.:
2 Event No.:
1 Event
Description:
PR NIS Channel N41 Fails High CRS/RO Identifies failed channel. Informs CRS.
Refers to S2.OP-SO.RPS-0001 (Q), Nuclear Instrumentation Channel Trip/Restoration to review actions for removing failed channel from service Notifies I/C Maintenance
~~
Reviews TS. Enters LCO 3.3.1.1 Actions 2 and 6 Coordinate to remove channel from service
- 1. DETECTOR CURRENT COMPARATOR, UPPER SECTION to PRN41
- 2. Verify CHANNEL DEFEAT lamp lit and OHA E-38 clears
- 3. DETECTOR CURRENT COMPARATOR, LOWER SECTION to PRN41
- 4. Verify CHANNEL DEFEAT lamp lit and OHA E-46 clears
- 5. POWER MISMATCH BYPASS to BYPASS PR N41
- 6. ROD STOP BYPASS to BYPASS PR N41
- 7. Verify 2RP1-OVERPOWER ROD STOP MANUAL BYPASS, CH 1 lit
- 8. Verify OHA E-31 clear
- 9. COMPARATOR CHANNEL DEFEAT to N41 IO. Verify COMPARATOR DEFEAT lit and OHA E-39 clear
- 11. At Control Rack No. 26, AXIAL FLUX DIFF MONITOR INPUT TEST SWITCH I toTEST
- 12. At Rack No. 2 Protection Ch Set I, A. Ensure OHA A-4 lit
- 6. Place Bistable Test Switches 2BS-41 I C and 2BS411 D in test (up) position
- 13. Remove both AC control Dower fuses from N41 drawer front Reduce turbine load, if needed to restore Tavg to program If desired. return ROD BANK SELECTOR SWITCH to AUTO Page4of I 1 NUREG-1021, Revision 9
~
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~
11 Op-Test No.:
1 Scenario No.:
2 Event No.: 2 Time Event
Description:
NE0 Reports Broken Snubber in Aux Building II Position Applicant's Actions or Behavior CRS CRS acknowledges report.
CRS CRS CRS Refers to TS. Enters 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action Statement for TS LCO 3.7.9.
Initiates action to repair snubber.
May declare affected subsystem inoperable.
Page 5 of 11 NUREG-1021, Revision 9
Op-Test No.:
1 Scenario No.: 2 Event No.: 3
- 1) Event
Description:
Main Turbine Governor Valve 24MS29 Fails Closed Determines that 24MS29 has closed. Informs CRS. Dispatches NE0 to investigate.
Refers to Precautions and Limitations of S2.OP-SO.TRB-0001 (Q),
Turbine Generator Startup Operations. Determines need to reduce power to 5 30% at 5% per minute. Implements S2.OP-AB.LOAD-0001 (a),
Rapid Load Reduction Initiates power reduction using rods and boration. Energizes pressurizer heaters. Maintains rods above Rod Insertion Limit.
Initiates turbine load reduction.
Time
~
CRS CRS PO Position CRSlROlPO Initiates activities to refill EHC reservior.
Notifies electric system operator and operations management.
Stops one condensate pump at -75% power.
NOTE: Insert Malf VL0447 (Remote #3) to fail 22BF19 closed after condensate pump is stopped during rapid power reduction or at lead examiner's discretion.
Applicant's Actions or Behavior Observe indications of valve closure:
- Megawatt load will drop rapidly as remaining governor valves open until limited by valve position limiter (VPL)
- Console Alarm TavglTref dev as Tavg rises.
- Steam Dumps will open to attempt to control Tavg
- Pressurizer pressure and level will rise due to change in Tavg, sprays open to control pressure Page 6 of 11 NUREG-I 021, Revision 9
Time Position PO Applicant's Actions or Behavior ResDonds to feedwater alarms andlor notes channes in BF19 Dosition.
PO CRS RO Page7of 11 Determines 22BF19 is closed, attempts to open in MANUAL, reports that it will not open.
Orders a manual reactor trip.
Manually trips reactor NUREG-1021, Revision 9 PO RO CRS Attempts to trip turbine. Determines turbine trip not functioning.
CRITICAL TASK # I Initiates MSLl before completion of reading of first 4 steps of EOP-TRIP-I.
Determines MSLl required. Manually initiates MSLIS lmdements EOP-TRIP-1
Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event
Description:
Loss of 2A 4KV Vital Bus Offsite sources. 21 EDG fails to auto connect with vital bus.
~~
~
Position CRS RO PO PO CRS CRS CRS Time
~
~~~~
Applicant's Actions or Behavior Performs initial actions of EOP-TRIP-1
- Trip Reactor (had to manually trip, 2 rods not fully inserted)
- Is Reactor Trip Confirmed
- Trip Turbine (turbine would not trip, MSlVs closed)
- Is ANY 4 KV Vital Bus energized (2A de-energized)
- Is SI Actuated (SI may be required if delay in closing MSIVs)
Reports reactor tripped manually, 2 rods not fully inserted Reports turbine not tripped, MSlVs closed Reports 2A 4KV Bus de-energized, 21 EDG running unloaded Transitions to EOP-TRIP-2 Makes page announcement - reactor trip Notifies SM of need to implement Emerclencv Classification Guide PO RO PO CRS Controls AFW flow to maintain >22E04 Ib/hr Verifies RCPs running, Tavg trending to 547"F, trip breakers open Manually closes 21 EDG output breaker, energizes 2A 4KV bus Directs reset of SEC
~
NOTE: Initiate 23 AFW Pump Trip and Loss of 21 EDG Page 8 of I1 NUREG-1021, Revision 9
Op-Test No.:
1 Scenario No.: 2 Event No.:
6 Time 11 Event
Description:
2 Control Rods Fail To Fully Insert On Reactor Trip Position Applicant's Actions or Behavior NOTE: Actions may not be taken as SI may actuate.
Reports that 2 control rods did not insert on the reactor trip.
Starts one BA PP in FAST RO RO RO RO Opens CV175 Closes 21 CV160 and 22CV160 RO Page 9 of 11 Ensure charging flow is maintained 787 gpm NUREG-1021, Revision 9
Position PO Applicant's Actions or Behavior PO reDorts loss of flow on 23 AFW PumD.
PO PO reports overspeed trip of 21 EDG.
CRS CRS/RO/PO Directs transition to FRHS-1 when SG level <9% with AFW flow ~22E04 lblhr Verifv RCS pressure > intact SG Dressure Op-Test No.: I Scenario No.:
2 Event No.:
7 Event
Description:
Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDG)
CRS RO RO Reviews Bleed and Feed initiation criteria with crew Stops all reactor coolant DumDs Resets SI Resets Phase A Isolation Resets Phase B Isolation Opens 21 CA330 and 22CA330 Resets each SEC Resets 230V Control Centers PO PO Verifies condensate system in operation ReDorts SGFP not available due to MSLl RO CRS PO PO Initiates SI Directs SI Verification per EOP-APPX-3 Closes 21 CN32 and 22CN32 Reports observed level increase in selected SG and/or CET temperatures lowerina
~~
CRITICAL TASK #2 Establish condensate flow into at least one SG.
~~
~~
Stops running RHR and SI pumps. Stops either 21 or 22 Charging Pump Determines SG to be depressurized.
Fully opens selected MSIO Directs NE0 to open selected BF40 or BF19 Page 10 of 11 PO PO NUREG-1021, Revision 9 Opens selected BF13 Opens 21 CN48 and 22CN48
Op-Test No.:
1 Scenario No.:
2 Event No.:
7 Event
Description:
Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDG)
NOT: Terminate scenario on lead evaluators direction after crew has determined that SI flow cannot be reduced.
Page 11 of 11 NUREG-1021, Revision 9
Amendix D Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.:
NRC #3 Op-Test No.: HOTEL Examiners:
Operators:
Initial Conditions:
3% Rated Thermal Power, MOL Turnover:
bonnet leak on Pzr Spray Bypass Valve 2PS4. Mode change is approved. Weather conditions are normal. Unit 1 and Hope Creek are at 100% power. Shift orders are to raise power to 50%
Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to Event 1
2 3
4 5
6 7
hour.
Malf. No.
PRO01 7A
~
SG0078A BF0105A RCOOl 2C SG0078A EL01 34 Event Type*
N CRS/PO R
RO I
CRS/RO C
ALL C
CRSlPO C
CRS/RO M
ALL C
CRSlRO I,
(R)eactivity, (1)nstrumer Event Descrhtion Raise Reactor Power Pressurizer Level Channel I (LT459) Fails Low (TS CRS)
~
21 SG Tube Leak (5 gpm) (TS CRS) 21 Main Feed Pump Trip 23 RCP High Vibration SGTR with Loss of Offsite Power Letdown Isolation Valve 2CV7 Fails to Close on Phase A Terminate when depress criteria met (SGTR-I Table F)
(C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9
SIMULATOR SETUP
- 1.
- 2.
INITIAL CONDITIONS I
Initialize simulator to 3% power IC Ensure CH I NOT selected on pressurizer level recorder Description PROOl7A, Pzr Lvl Ch I (LT459) Failure SG0078A, 21 SG Tube Leak BF0105A. 21 Main Feed Pump Trip RCOO12C, 23 RCP High Vibration EL01 34, Loss of Offsite Power' EVENT TRIGGERS I
Delay Ramp Remote Initial I Event Value No No 1 /No NA No No 2/No NA No No 3No NA No No 4/N0 NA No No 5/NO NA
- 1. I None I
1 ' Value Final I MALFUNCTION
SUMMARY
I I
I I
I I
4 True No No
- 1.
- 1.
- 2. -
Description Delay Ramp Remote Initial Final
/Event Value Value None
- 3.
No
- 1.
- 4.
Description Delay Ramp Remote Initial Final
/Event Value Value None
- 5. -
REMOTE FUNCTION
SUMMARY
I I
I I
UO OVERRIDE
SUMMARY
I I
I I
I I
Page 2 of 11 NUREG-1021, Revision 9
SIMULATOR OPERATOR NOTES I
After Event #5 (23 RCP High Vibration), ramp the severity of the SG tube leak from 5 gpm to 400 gpm over 3 minutes, then initiate the loss of offsite power.
Collect trend data on the following for evaluators:
21 and 22 SG pressure Pzr pressure 21 and 22 SG NR level Highest CET temperature NI power Page 3 of 11 NUREG-1021, Revision 9
Time Position CRS CRS CRS RO PO RO Page 4 of 11 Applicant's Actions or Behavior Directs activities associated with power increase IAW S2.OP-I0.Z-0003(Q), Hot Standby to Minimum Load:
- rod motion
- dilution Notifies chemistry to suspend 30 min RCS samples and 60 pressurizer samples Initiates Turbine Generator Startup Operations Adds positive reactivity
- rod motion
- dilution Places MSlOs in AUTO with setpoint 1010 to 1020 psig Blocks intermediate range and power range low power trips NOTE: Next event initiated after power increase has begun.
NUREG-1021, Revision 9
0 p-Tes t L Event D Position
- No.: I escription:
Applicant's Actions or Behavior Scenario No.:
3 Event No.:
2 Pressurizer Level Channel I (LT459) Fails Low RO Observes OHA. Identifies that Pzr Lvl Ch I has failed low.
Op-Test No.: I Event
Description:
L C RSlRO Refers to Alarm Response Procedure for OHA E-36 RO Takes manual control of charging, minimizes charging flow.
RO RO Selects an operable channel for control, alarm, and recorder.
Restores pressurizer heaters, as desired
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RO CRS RO Directs restoration of letdown IAW S2.OP-S0.CVC-0001 (Q), Charging, Letdown and Seal lniection Prepares for letdown restoration:
- 1.
Ensures letdown orifice isolations closed (2CV3,4, 5)
- 2.
Ensures 2CC71 in AUTO
- 3. Opens 2CV7, Ltdn Hx Inlet Vlv
- 4.
Places 2CV18 in MANUAL CLOSE
- 5.
Opens 2C18 until CLOSE (INC PRESS) p/b extinguishes
- 6.
Opens 2CV2, Ltdn Line lsol Vlv
- 7.
Places 2CV2 and 2CV277 (Ltdn Line Is01 Vlvs) in AUTO
- 8.
Places 2CV55 in MANUAL and ADJUSTS chg flow 85-90 gpm
- 9.
Returns 2CA2015, Control Air Supply to CV55 Byp Vlv to NORMAL IO. Adjust 2CV71, as necessary, to maintain 6-12 gpm per pump, not to exceed 40 gpm total RCP seal injection flow Restore letdown:
I. Simultaneously
- Opens 75 gpm letdown orifice isolation (2CV4 or 2CV5)
- Adjusts 2CV71 for 6 to 12 gpm per pump
- Adjusts 2CV18 to maintain letdown pressure at 300 psig
- 2.
Ensures Master Lvl Controller in AUTO
- 3.
Ensures pzr level within normal band, places 2CV55 in AUTO
- 4.
Adjusts 2CV18 as necessary and places in AUTO CRS Contacts I&C to place pressurizer channel in tripped condition CRS Page 5 of I 1 Enters TS LCO 3.3.1.I Action 6. May review post accident monitoring TS (only 2 channels required).
NUREG-1021, Revision 9
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Op-Test No.: I Scenario No.:
3 Event No.:
3 Event
Description:
21 SG Tube Leak (5 gpm)
Time
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Position Applicant's Actions or Behavior PO CRS CRS CRS Reports increasing activity in condenser offgas and 21 SG Refers to AB.RAD-0001 (a),
Abnormal Radiation Announces increasing activity on 21 SG Notifies SM to refer to Emerclencv Classification Guide II CRS PO I CRS Refers to AB.SG-0001 (a), xxxxx xxxx.
I xxxx I CRS CRS Enters TS LCO 3.4.7.2.c. Action b. for greater than 1 gpm total SG tube leakage and greater than 500 gpd tube leakage in single SG (4 hrs to fix or next 6 to Hot Stby)
II I
I NOTE:
Page 6 of 11 NUREG-1021, Revision 9
Time Position CRS CRS NOTE If CRS chooses to manually trip reactor, initiate the next I malfunction.
Applicant's Actions or Behavior Recognizes trip of the operating main feedwater pump. Enters S2.OP-AB.CN-0001 (Q), Main Feedwater / Condensate System Abnormality..
Verifies reactor power P-10 setpoint. Proceeds to Step 3.14.
I CRS I
Directs RO to reduce power to <5%.
- 5. Sets SG Inlet Vlv demand to 0% (Vlvs 21 through 24AF21)
- 6. Starts 21 and 22 AFW pumps
- 7. Controls 21 through 24AF21 to maintain SG levels within 555% of Droaram level (-35% NR levell NOTE Initiate the next malfunction after SG level control established on AFW.
Page 7 of 11 NUREG-1021, Revision 9
Op-Test No.:
1 Scenario No.:
3 Event No.:
5 Event
Description:
23 RCP High Vibration Time Position Applicant's Actions or Behavior Observes OHA D-36 RCP VIB HI alarm. Refers to S2.0P-AR.Z-0004(Q), Overhead Annunciators Window D.
- If reactor already tripped, then CRS will direct stopping #23 Page 8 of 11 NUREG-1021, Revision 9
Time Position Amlicant's Actions or Behavior RO/PO CRS CRS/RO/PO CRS PO Observe indications of increased rate of 21 SG tube leakage. Informs CRS.
Directs manual SI actuation. Makes page announcement. Transitions to Perform immediate actions of EOP-TRIP-1.
Confirms operability of 4KV vital buses following loss of offsite power, remains in EOP-TRIP-1.
Blocks and resets SECs EOP-TRIP-1.
RO PO PO Verifies no RCPs running and Tavg 647. (Step 21)
Throttles AFW to maintain SG NR levels 9-35% fSteD 21 Verify valves closed on ruptured SG (Step 4)
MS167 MS Stop MS18 MS Bypass MS7 MS Drain GB4 SG Outlet PO Initiates MSL Isolation on loops 21 through 24 (Step 21)
CRITICAL TASK #2 Isolate AFW to the ruptured SG within 10 minutes of initiation of Safety Injection signal.
I PO CRS Resets SI, Phase A, Phase B, SECs, and opens cntmt control air isolation valves (21 CA330 and 22CS330). Resets 230V Control Centers (Step I IO,.
Isolates AFW to 21 SG Determines 21 SG level increasing in an uncontrolled manner.
Transitions to EOP-SGTR-1 (Step 27)
PO I
Stops feeding 21 SG (Step 6)
Page 9 of 11 NUREG-1021, Revision 9 CRS PO Determines target cooldown CET temperature from Table D.
Cooldowns at max rate using intact SG MSIO valves. Stops cooldown at target temperature.
PO
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Op-Test No.: 1 Scenario No.:
3 EventNo.:
6 Event
Description:
SGTR with Loss of Offsite Power II I
I It NOTE: Terminate when depress criteria met (SGTR-1Table F) or at I discretion of lead examiner.
Page 10 of 11 NUREG-1021, Revision 9
Time Position ADDlicant's Actions or Behavior Page 11 of 11 PO PO NUREG-1021, Revision 9 Determines 2CV7 not closed (Step 10 EOP-TRIP-1).
Closes 2CV7 using handswitch.
NOTE: Terminate when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.
Amendix D Form ES-D--l Event No.
1 Facility:
SALEM 1 & 2 Scenario No.:
NRC #4 Op-Test No.: HOTEL Examiners:
Operators:
Initial Conditions:
Turnover:
two hours ago for motor bearing replacement. All required surveillances are complete.
Weather conditions are normal. Unit 1 and Hope Creek are at 100% power. Shift orders are to reduce power to 60% at 10% per hour to repair SGFP oil leak.
100% Rated Thermal Power Unit at 100% power. 22 SGFP has a control oil leak. 22 AFW Pump taken 00s Malf. No.
Event Type*
Event Description N: cRslpo R: RO Reduce Power to 60% To Repair SGFP Oil Leak 6
7
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11 2 I SG0095D I I 24 SG Lvl Xmtr (549) Ch II Fails Low (TS-CRS)
MS0088D M
24 MSL Break In Containment, 24 MSIV Fails to Close MS0092H ALL SJ0184A C
21 SI Pump Fails to Auto Start CRSlPO CVOO29A 11 I
1 CRtRO I Letdown Hx CCW Outlet 2CC71 Fails Closed 9
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I Cntmt Area Hi Rad Monitor 2R44B Fails High [TS-CRS]
RP0277A C
Containment Spray Fails to Automatically Actuate RP0277B CRSlPO 22 Fd Pump Trip wlUncontrolled Rod Insertion in AUTO BFOIOSB C
)I 1
RD0045 1 CRSIRO RP0276A C
Phase B Fails to Automatically Actuate 11 I RP0276B I CRSlPO 1
Page 1 of 14 NUREG-1021. Revision 9
SIMULATOR SETUP
- 1.
- 2.
INITIAL CONDITIONS I
Initialize simulator to IC-181, 100% power, BOL, C, 1152 ppm Clearance tag 22 AFW Pump NA NA NA NA NA EVENT TRIGGERS I
I True True True True True
- 1.
I None
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- 9.
- 10.
MALFUNCTION
SUMMARY
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RM0241A, Cntmt Area Hi Rad Monitor No No 3/NO 2R44B Fails Hi BFOl05B, 22 Stm Gen Feed Pump Trip No No 4/NO No RD0045, Uncontrolled Rod Insertion In Auto MS0088D, Mn Stm Line (24SG) Rupture Description
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No No 4/NO No No 5h.b RP0276A, Phase B Fails to Automatically Actuate RP0276B, Phase B Fails to Automatically Actuate Delay Ramp Remote I Event No No No/No No No No/No I
No I No I No/No RP0277A, Containment Spray Fails to Automatically Actuate RP0277B, Containment Spray Fails to Automatically Actuate SJO184A, 21 SI Pump Fails to Auto Start MS0092H, 24MS167 (MSIV) Fails Open No No/No No/No I
N O T GNO SG0095D, 24 SG Lvl Xmtr (549) Ch II I No 1
No I UNO I I Fails CV0029A, Letdown Hx CCW Outlet 18-I 2CC71 Fails Closed I
No I No I 2/No NA True NA True NA True NA True NA 0
Page 2 of 14 NUREG-1021, Revision 9
REMOTE FUNCTION
SUMMARY
r 110 OVERRIDE
SUMMARY
I I
I I
I I
No Description None Description Delay Ramp Remote Initial Final
/Event Value Value AF0025D, 22 AFW Pump Bkr Control Power AF0026D, 22 AFW Pump Rack Out 2* I I
I I
Delay I Ramp 1 7;;:;
1 Initial Value No/No Value Final I SIMULATOR OPERATOR NOTES I
Collect trend data on the following for evaluators:
Reactor power Turbine Generator load (MW) 21 and 24 SG NR level 21 and 24 SG WR level 21 and 24 SG pressure Containment pressure 21 and 24 SG AFW flow VCT outlet temperature Page 3 of 14 NUREG-1021, Revision 9
Time Position CRS CRS Applicant's Actions or Behavior Implements S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction Notifies electric system oDerator and oDerations manaaement.
Page 4 of 14 RO PO PO NUREG-1021, Revision 9 Initiates power reduction using rods and boration. Energizes pressurizer heaters. Maintains rods above Rod Insertion Limit.
Initiates turbine load reduction.
Stops one condensate pump at -75% power.
Op-Test No.:
1 Scenario No.:
4 Event No.: 2 Event
Description:
24 SG Lvl Xmtr (549) Ch II Fails Low Position RO/PO RO/PO CRS CRS CRS Time
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Applicant's Actions or Behavior Observes Bezel Alarm for Protection Level Lo-Lo on 24 SG and SG low level lights on 2RP4.
Identifies failure low of 24 SG Level Ch II (549). Informs CRS. Refers to S2.OP-AR.ZZ-O014(Q), Control Console 2CC2.
Notifies Maintenance Controls to remove inoperable channel from service IAW S2.0P-SO.RPS-O004(Q), Placing Steam Generator Channel in Tripped Condition.
Refers to TS. Enters TS LCO 3.3.1.I Item 14 Action 6 Initiates action to reDair channel.
Page 5 of 14 NUREG-1021, Revision 9
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Position Applicant's Actions or Behavior RO Observes OHA E-41, LTDWN HX OUT TEMP HI. Informs CRS. Refers to S2.OP-AR.ZZ-O005(Q), Overhead Annunciator Window E.
Verifies 2CV21 indicates Mixed Bed diversion to VCT at 2CC2.
Places 2CC71 in manual and attempts to adjust letdown temperature to
= 100°F.
RO RO
~
RO Determines that 2CC71 remains closed. Checks status of breaker 2ADC2AX7 (2CC113,2CC215, & 2CC171 LETDOWN DISCHARGE VALVES; located in 2AADC 125VDC Distribution Cabinet).
NOTE: RO will receive report that 2ADC2AX7 did not open. Breaker is closed.
Directs placing excess letdown in service IAW S2.OP-SO.CVC-O003(Q),
I Excess Letdown Flow.
CRS RO RO RO RO RO RO Ensures open 2CC215, Excess Letdown HX Inlet.
Opens 2CC113, Excess Letdown HX Outlet.
Ensures closed 2CV132, Excess Letdown Selects 2CV134, Flow to VCT Opens 2CV278 and 2CV131, Excess Letdown Slowly throttles open 2CV132, Excess Letdown and maintains temperature 495F and pressure < I 50 psig while warming system.
RO CRS Adjusts 2CV132 to attain desired ffowrate.
Directs securing of normal letdown IAW S2.OP-S0.CVC-0001 (a),
Charging, Letdown and Seal Injection.
RO I Places 2CA2015, Control Air Supply to CV55 Bypass in BYPASS RO I Adjusts 2CV71 for 6-12 gpm injection per pump.
RO Closes the following valves:
2CV3,2CV4 and 2CV5, Letdown Orifice Isolation Valves 2CV2 and 2CV277, Letdown Line Isolation Valves 2CV7, Letdown HX Inlet Valve Page 6 of 14 NUREG-1021, Revision 9
Op-Test No.:
1 Scenario No.:
4 Event No.:
3 Event
Description:
Letdown Hx CCW Outlet 2CC71 Fails Closed I
I NOTE: Procedural path is listed above. However, CRS should direct the securing of normal letdown prior to establishing excess letdown in order to protect the VCT and RCP seals from excessive temperature. Precaution in S2.OP-SO.RC-O001(Q) Reactor Coolant Pump Operations states the following:
Normal Seal Injection water temperature is SI 30°F. Seal Injection water temperature of up to 190°F is permitted only if RCS temperature is ~400°F.
Page 7 of 14 NUREG-1021, Revision 9
Time Position Applicant's Actions or Behavior PO Identifies Cntmt Area Hi Rad Monitor 2R44B (Stairway to Reactor Sump -
96' Elevation) has failed high. Informs CRS.
Implements S2.OP-AB.RAD-0001 (Q), Abnormal Radiation.
Determine radiation alarm is not valid.
CRS CRS/PO Page 8 of 14 CRS CRS NUREG-1021, Revision 9 Refers to TS and ODCM.
Enters TS LCO 3.3.6 Item 1.b. Action 26 for inoperable containment area
Op-Test No.: 1 Scenario No.:
4 Event No.:
5 Event
Description:
22 Feed Pump Trip wlUncontrolled Rod Insertion in AUTO I
I Time Position Applicant's Actions or Behavior I
I RO/PO I Observes trip of 22 SG Feed Pump. Inform CRS.
I I
I CRS I
Page 9 of 14 NUREG-1021, Revision 9
Time Position Page I O of 14 Applicants Actions or Behavior NUREG-I 021, Revision 9
Page I I of 14 NUREG-1021, Revision 9
Op-Test No.: 1 Scenario No.: 4 Event No.: 7
)I Event
Description:
21 SI Pump Fails to Auto Start I
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(1 Time I Position Applicant's Actions or Behavior Page 12 of 14 NUREG-1021, Revision 9
Op-Test No.:
1 Scenario No.: 4 Event No.: 8 II Time Position Applicant's Actions or Behavior Page 13 of 14 NUREG-I 021, Revision 9
Op-Test No.:
1 Scenario No.:
4 Event No.:
9 Event
Description:
Containment Spray Fails to Automatically Actuate 11 Time I Position I
Amlicant's Actions or Behavior Page 14 of 14 NUREG-1021, Revision 9